Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing November 17, 2010 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259 Subject: Browns Ferry Nuclear Plant, Unit 1, Core Operating Limits Report for Cycle 9 Operation In accordance with the requirements of Technical Specification 5.6.5.d, the Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant, Unit 1, Cycle 9, Core Operating Limits Report (COLR). The Unit 1, Cycle 9, COLR includes all modes of operation (Modes 1 through 5). There are no new commitments contained in this letter. If you have any questions, please contact Tom Matthews at (423) 751-2687. Respectfully, R. M. Krich Enclosure: Core Operating Limits Report, (105% OLTP), for Cycle 9 Operation TVA-COLR-BF1 C9, Revision 0, dated October 2010 cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant printed on recycled paper (U-
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Tennessee Valley Authority1101 Market Street, LP 3RChattanooga, Tennessee 37402-2801
R. M. KrichVice PresidentNuclear Licensing
November 17, 2010
10 CFR 50.4
ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001
In accordance with the requirements of Technical Specification 5.6.5.d, the TennesseeValley Authority is submitting the Browns Ferry Nuclear Plant, Unit 1, Cycle 9, CoreOperating Limits Report (COLR). The Unit 1, Cycle 9, COLR includes all modes ofoperation (Modes 1 through 5).
There are no new commitments contained in this letter. If you have any questions,please contact Tom Matthews at (423) 751-2687.
Respectfully,
R. M. Krich
Enclosure: Core Operating Limits Report, (105% OLTP), for Cycle 9 OperationTVA-COLR-BF1 C9, Revision 0, dated October 2010
cc (Enclosure):NRC Regional Administrator - Region IINRC Senior Resident Inspector - Browns Ferry Nuclear Plant
printed on recycled paper (U-
Enclosure
Tennessee Valley AuthorityBrowns Ferry Nuclear Plant
Unit I
Core Operating Limits Report, (105% OLTP), for Cycle 9 OperationTVA-COLR-BF1C9, Revision 0, dated October 2010
Browns Ferry Unit I Cycle 9Core Operating Limits Report, (105% OLTP)
TVA-COLR-BFIC9 Revision o (Finai)(OVtobe 010, P§00 V
October 2010
Prepared:, ;W.-, 9r _ ý i- Date:
Date: 0,,•-ii'ý ýohefl, E~ngineerVerified,
6,(. .....itApproved: / .Date,
BWR Fuel EngineeringG. C, Storey, Mai
36ek, Manager, Reator EngineeringDate; / Aozo/O_
Approved:
U
Nuclear Fuel Engineering - BWRFE
NPG Date: October 15, 2010
1101 Market Street Chattanooga, TN 37402 EDMS: L32 101015 801
Table of ContentsTotal Number of Pages = 38 (including review cover sheet)
L is t o f T a b le s . ................................................................................................................................................ iiiL ist o f F ig u re s ................................................................................................................................................ iv
R e v is io n L o g ................................................................................................................................... vN o m e n c la tu re ................................................................................................................................................ v iReferences .................................................................................................... ................... ...... ....... viii
1 In tro d u c tio n ........................................................................................................................... 11 .1 P u rp o s e ......................................................................................................................... 11 .2 S c o p e ............................................................................................................................ 11.3 Fuel Loading .................................................................................................................. 11.4 Acceptability .................................................................................................................. 1
2 APLHG R Lim its .................................................................................................................... 32.1 Rated Power and Flow Lim it: APLHG RRATED ........................................................... 32.2 Off-Rated Power Dependent Lim it: APLHG Rp ......................................................... 32.3 Off-Rated Flow Dependent Lim it: APLHGRF ........................................................... 32.4 Single Loop O peration Lim it: APLHG RSLO ............................................................... 32.5 Equipment Out-Of-Service Corrections .................................. 5
3 LHG R Lim its ......................................................................................................................... 63.1 Rated Power and Flow Lim it: LHGRRATED ................................................................ 63.2 Off-Rated Power Dependent Lim it: LHG Rp ............................................................. 63.3 Off-Rated Flow Dependent Lim it: LHG RF ................................................................ 63.4 Single Loop O peration Lim it: LHG RSLO ........................................................................ 63.5 Equipm ent O ut-Of-Service Corrections .................................................................... 6
4 O LM CPR Lim its ................................................................................................................. 144.1 Rated Power and Flow Lim it: M CPRRATED ............................................................. 14
4.1.1 Scram Tim ing Dependence ............................................................................ 144.1.2 Equipment O ut-Of-Service (EOOS) Options .................................................. 154.1.3 Exposure Dependent Lim its ............................................................................ 15
4.2 Flow Dependent M CPR Lim it: M CPRF .................................................................. 164.3 Single Loop O peration Lim it: M CPRSLO .................................................................. 164.4 Power Dependent M CPR Lim it: M CPRp ............................................................... 16
5 APRM Flow Biased Rod Block Trip Settings .................................................................. 246 Rod Block M onitor (RBM ) Trip Setpoints and Operability ........................ ......................... 257 Shutdown Margin Lim it .................................................................................................. 27
APLHGRRATED ............................................................................................................................... 4LHGRRATED for GE14 U0 2 Fuel ............................................................................................... 8LHGRFACp for All EIS or RPTOOS Conditions ........................................................................ 9LHGRFACp for TBVOOS Conditions ..................................................................................... 10LHGRFACp for PLUOOS Conditions ..................................................................................... 11LHGRFACP for RPTOOS, TBVOOS, and PLUOOS Conditions ............................................ 12L H G R F A C F ................................................................................................................................. 1 3M C P R F ........................................................................................................................................ 1 7MCPRRaed: BOC to MOC Exposure ..................................................................................... 18MCPRRated: BOC to EOC Exposure ....................................................................................... 19Kp M ultiplier and MCPRp for All Equipment In Service or RPTOOS ...................................... 20Kp M ultiplier and MCPRp for TBVOOS .................................................................................. 21Kp M ultiplier and M CPRp for PLUOOS .................................................................................. 22Kp Multiplier and MCPRp for RPTOOS, TBVOOS, and PLUOOS ......................................... 23
License Condition of OperationLoss of Feedwater HeatingLHGR Multiplier (Power or Flow dependent)Low Power Range MonitorGenerator Load Reject, No Bypass
kW
LCOLFWHLHGRFACLPRMLRNB
MAPFAC MAPLHGR multiplier (Power or Flow dependent)MCPR Minimum CPR
Moisture Separator Reheater ValveMSRV OOSMetric Ton UraniumMega Watt Day per Metric Ton Uranium
Near EOCUnited States Nuclear Regulatory CommissionNominal Scram SpeedNominal TSP
MCPR Operating LimitOut-Of-ServiceOscillation Power Range Monitor
Period Based Detection AlgorithmPower, below which TSV Position and TCV Fast Closure Scrams are BypassedPower Load UnbalancePLU OOSPower Range Neutron Monitor
Rod Block MonitorReactor Protection SystemRecirculation Pump TripRPT OOS
2. 0000-0077-8380-SRLR, Revision 0, Supplemental Reload Licensing Report BrownsFerry 1 Reload 7 Cycle 8, Global Nuclear Fuels, Inc., August 2008.
3. 0000-0044-1520-SRLR, Revision 0, Supplemental Reload Licensing Report BrownsFerry 1 Reload 6 Cycle 7, Global Nuclear Fuels, Inc., January 2007.
4. 0000-0113-6833-FBIR, Revision 0, Fuel Bundle Information Report Browns Ferry I
Reload 8 Cycle 9, Global Nuclear Fuels, Inc., September 2010.
Methodoloqy References
5. NEDE-24011-P-A-16, General Electric Standard Application for Reactor Fuel,October 2007.
6. NEDE 724011-P-A-16-US, General Electric Standard Application for Reactor Fuel(Supplement for United States), October 2007.
PRNM Setpoint References
7. Filtered Setpoints - EDE-28-0990 Rev. 3 Supplement E, "PRNM (APRM, RBM, andRFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] forTennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.
8. Unfiltered Setpoints - EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, RBM, andRFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] forTennessee Valley Authority Browns Ferry Nuclear Plant", October 1997.
9. GE Letter LB#: 262-97-133, Browns Ferry Nuclear Plant Rod Block Monitor SetpointClarification - GE Proprietary Information, September 12, 1997.
10. NEDC-32433P, Maximum Extended Load Line Limit and ARTS ImprovementProgram Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3, GE NuclearEnergy, April 1995.
I IntroductionIn anticipation of cycle startup, it is necessary to describe the expected limits of operation.
1.1 Purpose
The primary purpose of this document is to satisfy requirements identified by unit technicalspecification section 5.6.5. This document may be provided, upon final approval, to the NRC.
1.2 Scope
This document will discuss the following areas:
> Average Planar Linear Heat Generation Rate (APLHGR) Limit(Technical Specifications 3.2.1 and 3.7.5)
> Linear Heat Generation Rate (LHGR) Limit(Technical Specification 3.2.3, 3.3.4.1, and 3.7.5)
> Minimum Critical Power Ratio Operating Limit (OLMCPR)(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)
> Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting(Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)
> Rod Block Monitor (RBM) Trip Setpoints and Operability(Technical Specification Table 3.3.2.1-1)
The core will contain all Global Nuclear Fuels, Inc., GE14 fuel. Nuclear fuel types used in thecore loading are shown in Table 1.1. The core shuffle and final loading were assessed todetermine Reference 1 applicability relative to minor loading changes.
1.4 Acceptability
Limits discussed in this document were generated based on NRC approved methodologies perReferences 5 through 6.
GE 1 4-P1 ODNAB408-17GZ-1 OOT-1 50-T6-3366 9 16 19 JYP337-JYP352
The table identifies the expected fuel type breakdown in anticipation of final core loading. The final composition of the core depends uponuncertainties during the outage such as discovering a failed fuel bundle, or other bundle damage. Minor core loading changes, due tounforeseen events, will conform to the safety and monitoring requirements identified in this document.
2.5 Equipment Out-Of-Service CorrectionsThe limit shown in Figure 2.1 is applicable for operation with all equipment In-Service as well asthe following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*
In-ServiceRPTOOSTBVOOS
PLUOOSFHOOS (or FFWTR)
All equipment In-ServiceEOC-Recirculation Pump Trip Out-Of-ServiceTurbine Bypass Valve(s) Out-Of-ServicePower Load Unbalance Out-Of-ServiceFeedwater Heaters Out-Of-Service or Final FeedwaterTemperature Reduction
Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to therated APLHGR limits as described previously.
The rated conditions LHGR is identified in Reference 4, and shown in Figure 3.1 for U0 2 fuel.
Separate, concentration dependent limits apply for rods containing Gadolinium; LHGR limits are
provided in Reference 4.
3.2 Off-Rated Power Dependent Limit: LHGRp
LHGR limits are adjusted for off-rated power conditions using the LHGRFACp multiplierprovided in Reference 1. The multiplier is dependent on EOOS conditions. Consequently, themultipliers are shown in Figure 3.2 thru Figure 3.5, for various EOOS conditions/combinations.
3.3 Off-Rated Flow Dependent Limit: LHGRF
LHGR limits are adjusted for off-rated flow conditions using the LHGRFACF multiplier providedin Reference 1. There are no EOOS dependencies for the multiplier. The multiplier is shown in
Figure 3.6.
3.4 Single Loop Operation Limit: LHGRSLO
The single loop operation multiplier is 0.93, per Reference 1.
3.5 Equipment Out-Of-Service CorrectionsThe limit shown in Figure 3.1 is applicable for operation with all equipment In-Service as well asthe following Equipment Out-Of-Service (EOOS) options; including combinations of the options.*
OLMCPR is calculated to be the most limiting of the flow or power dependent values
OLMCPR limit = MAX ( MCPRF, MCPRp )
where:MCPRp
MCPRFMCPRSLO
off-rated power MCPR limitoff-rated flow MCPR limitSLO MCPR limit
[MCPRRATED * KpJ
[MCPRp + SLO Adder]
4.1 Rated Power and Flow Limit: MCPRRATED
The rated conditions MCPR is identified in Reference 1. The rated power and flow limits forvarious cycle exposure windows, and EOOS scenarios, are shown in Figure 4.2 & Figure 4.3.
OLMCPR is calculated to be the most limiting of the flow or power dependent values.
4.1.1 Scram Timing Dependence
The MCPRRATED has a scram timing dependence which is assessed after control blade timingshortly after startup, and is discussed as follows:
T = 0.0 or,
T ave r TBwhichever is greater
TA- TB
where: TA = 1.096 sec (analytical Option A scram time limitbased on dropout time for notch position 36)
where: = 0.830 sec (mean scram time used in transient analysisbased on dropout time for notch position 36)
(Y = 0.019 sec (standard deviation of pt)
N = Total number of active rods measured in Technical SpecificationSurveillance Requirement SR 3.1.4.1
n = Number of surveillance rod tests performed to date in cycle
1= Scram time (dropout time) from fully withdrawn to notch position36 for the ith rod
For reactor startup, Option A limits (T=1.0) shall be used prior to the determination of T inaccordance with SR 3.1.4.1.
4.1.2 Equipment Out-Of-Service (EOOS) Options
All equipment service conditions support 1 SRVOOS. EOOS options, including combinations,covered by MCPRp limits are given by the following:
In-ServiceRPTOOSTBVOOSPLUOOSFHOOS (or FFWTR)
All equipment In-ServiceEOC-Recirculation Pump Trip Out-Of-ServiceTurbine Bypass Valve(s) Out-Of-ServicePower Load Unbalance Out-Of-ServiceFeedwater Heaters Out-Of-Service (or FinalFeedwater Temperature Reduction)
4.1.3 Exposure Dependent Limits
Exposures are tracked on a cycle exposure basis. Higher exposure limits are always morelimiting, and may be used for any cycle exposure up to the ending exposure. Cycle ExposureRanges are defined as follows:
BOC to MOC: where MOC corresponds to EOR* - 3208 MWd/MTU (2910 MWd/ST).BOC to EOC
EOC exposure includes cycle extension options such as final feedwater reduction (FFTR) andpower coastdown.
EOR is defined as the end of rated power capability for rated core flow and nominal feedwater temperature conditions.
MCPRF limits are dependent upon core flow (% of Rated), and the max core flow limit, (Rated orIncreased Core Flow, ICF). MCPRF limits are shown in Figure 4.1, per Reference 1. Limits arevalid for all EOOS combinations. No adjustment is required for SLO conditions.
4.3 Single Loop Operation Limit: MCPRSLO
The single loop operation adder is 0.02, per Reference 1.
4.4 Power Dependent MCPR Limit: MCPRp
MCPRp limits are dependent upon core power level (% of Rated) and EOOS conditions. KpMultipliers and/or MCPRp values are provided in Figure 4.4 thru Figure 4.7. Determination ofpower dependent MCPR is differentiated relative to Pbypass (30% Rated Power) as follows:
6 Rod Block Monitor (RBM) Trip Setpoints and Operability(Technical Specification Table 3.3.2.1-1)
The RBM trip setpoints and applicable power ranges, based on References 7 & 8, are shown inTable 6.1. Setpoints are based on an HTSP, unfiltered analytical limit of 117%. Unfilteredsetpoints are consistent with a nominal RBM filter setting of 0.0 seconds; filtered setpoints areconsistent with a nominal RBM filter setting less than 0.5 seconds.
Generic CRWE based OLMCPR values were reported and verified per References 7, 8, 9, and10. However, Reference 10 generic values were developed assuming a SLMCPR < 1.07.Consequently, cycle specific CRWE analyses were performed to support the current SLMCPR;values are reported in Reference 1. Cycle specific analysis results indicate the SLMCPRremains protected for RBM inoperable conditions (i.e., unblocked). RBM setpoints in TechnicalSpecification Table 3.3.2.1-1 are applicable as shown in Table 6.2.
Table 6.2 RBM Setpoint Applicability
Thermal Power Applicable Notes from(% Rated) MCPRt Table 3.3.2.1-1 Comment
> 27% and < 90% < 1.70 (a), (b), (f), (h) two loop operation
< 1.72 (a), (b), (f), (h) single loop operation
-> 90% < 1.40 (g) two loop operationt
Values are considered maximums. Using lower values, due to RBM system hardware/software limitations, is conservative, and acceptable.
t -MCPR values shown correspond with, (support), SLMPCR values identified in Reference 1.
Greater than 90% rated power is not attainable in single loop operation.
Results, compared against the base case OLMCPR results of Reference 1, indicate SLMCPRremains protected for RBM inoperable conditions (i.e., unblocked).
Assuming the strongest OPERABLE control blade is fully withdrawn, and all other OPERABLEcontrol blades are fully inserted, the core shall be sub-critical and meet the following minimumshutdown margin:
SDM > 0.38% dk/k
Bmwns Ferry Unit 1 Cyde 9 Page 27
Browns Ferry Unit R Cycle 9Core Operating Limits Report, (1105% OLTP)
The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.
Table 3.3.1.1-1, Function 2f, identifies the OPRM upscale function. This function must be
operable in conjunction with the following surveillance requirements:
SR 3.3.1.1.1SR 3.3.1.1.7SR 3.3.1.1.13SR 3.3.1.1.16SR 3.3.1.1.17
Background
Browns Ferry uses the Option III stability Detect and Suppress solution as part of the PRNMsystem. The Option Ill system is based upon combining groups of local LPRM's into cellsknown as OPRM's. The OPRM's generate a combined LPRM signal that is examined for thecharacteristics of a reactor instability event, and if detected, a reactor trip is generated.
The PBDA is the licensing basis portion of the Option III system, requiring a cycle-specificcalculation to determine the amplitude setpoint to generate a reactor trip in time to protect the
fuel from exceeding the SLMCPR.
The OPRM Upscale Trip function is required to be operable when the plant is in a region of
power-flow operation where actual thermal-hydraulic oscillations might occur (T.S. enabled region ,
greater than 25% rated thermal power and loss than 60% reclrculation drive flow).
Setpoints
Instrument setpoints are established such that the reactor will be tripped before an oscillationcan grow to the point where the SLMCPR is exceeded. An Option III stability analysis is
performed for each reload core to determine allowable OLMCPR's as a function of OPRM
setpoint. Analyses consider both steady state startup operation, and the case of a two
recirculation pump trip from rated power.
The resulting stability based OLMCPR's are reported in Reference 1. The OPRM setpoint(sometimes referred to as the Amplitude Trip, Sp) is selected such that required margin to the SLMCPR
is provided without stability being a limiting event. Analyses are based on cycle specific
DIVOM analyses. The calculated OLMCPR's are shown.in Table A.1. Review of results,
relative to the base case operation shown in Figure 4.2 indicates an OPRM setpoint of 1.15 can
be supported. Extrapolation beyond a setpoint of 1.15 is not allowed.
Should the Option III system be declared inoperable, alternate methods/procedures (i.e.,stability ICA's) are incorporated restricting plant operation in the high power, low core flowregion of the power/flow map. ICA's contain specific operator actions, providing clearinstructions (depending upon the plant type) for operator response to a reactor inadvertently (orunder controlled conditions) entering any of the defined regions. ICA's provide appropriateguidance to reduce the likelihood of hydraulic instability, and enhance early detection in the veryunlikely event a stability threshold is exceeded in spite of the ICA guidelines.
In July 2002, GE recommended the original ICAs, established generically in 1994, be re-evaluated to assure adequate conservatism, given the trend to higher energy cores and moreaggressive fuel management strategies. The recommended replacement regions and theassociated calculational procedure are referred to as BSP, and need to be confirmed on aplant/cycle specific basis. The vendor has performed an ICA/BSP confirmation calculationusing NRC approved methods.
Based upon the above discussion, appropriate stability analyses and evaluations have beenperformed to satisfy licensing requirements.